ML17345B281
| ML17345B281 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 09/20/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| References | |
| NUDOCS 8310030659 | |
| Download: ML17345B281 (18) | |
Text
Docket Nos.
50-250 and 50-251
- SP 2~ l9N Dr. Robert E. Uhrig, Vice President Advanced Systems and Technology Florida Power and Light Company Post Office Box 14000 Juno
- Beach, Florida 33408
Dear Dr. Uhrig:
Subject:
Revised Inservice Test Program for Pumps and Valves By letters dated October 27, 1982 and March 7, 1983, you requested revision of your existing pump and valve Inservice Testing Program for Turkey Point Plant Uni,ts 3 and 4.
This request is to ensure the program is in accordance with the applicable ASME Code and Addenda as required by 10 CFR 50.55, "Codes and Standards."
We are reviewing your proposed inservice test program and reflief requests for the next ten year interval.
In order to continue our
- review, we request a site visit.
The enclosed questions and comments will serve as. the agenda for. our site visit.
We request that the arrangements and details be made by telephone and the site visit be at the earliest time agreeable to both our staffs.
Sincerely,
Enclosure:
As stated
'L:ORB 1
DMcDonald:cc 9/ 8/83 a
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cc w/enclosure:
See next page Original signed bye Bo JL. Varga Steven A. Varga, Chief Operating Reactors Branch No.
1 Division of Licensing DISTRIBUTION:
NRC PDR Local PDR ORB81 Reading D. Eisenhut OELD E. Jordan D. McDonald C. Parrish J. Taylor ACRS (10)
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Page F.
Cherny 83i0030659 830920 PDR ADQCK 05000250 P
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Robert E. Uhrig Florida 'Power and Light Company CC ~
Harold F. Reis, Esquire Lowenstein, Newman, Reis and Axelrad 1025 Connecticut
- Avenue, N.W.
Suite 1214 Washington, D. C.
20036 Norman A. Coll, Esquire
- Steel, Hector and Davis 1400 Southeast First National Bank Building Miami, Florida 33131 Mr. Henry Yaeger, Plant Manager Turkey Point Plant Florida Power and Light Company
'P. 0; Box 013100 Miami, Florida
- 33101, Mr.. Jack Shreve Office of the Public Counsel Room 4, Holland.Building Tallahassee, Florida 32304 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Resident Inspector Turkey Point Nuclear Generating Station U. S. Nuclear Regulatory Commission Post Office Box 1207 Homestead, Florida 33030 James P. O'Reilly Regional Administrator - Region II U. S. Nuclear Regulatory Commission 101 Marietta Street - Suite 3100 Atlanta, Georgia 30303
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TURKEY POINT UNITS 3 AND 4 IST PROGRAM REVIEW QUESTIONS ANO COMMENTS, A.
General Ouestions and Comments 1.
Is Note 2 of Section I.E."a request for relief from the requirements of paragraph IWV-3417(b) of Section XI?
,2.
Provide a clarifi.cation.of Note 3 of Section I.E. of the Turkey Point IST Program.
- 3. 're all Category A or A/C valves listed in the IST programs leak rate tested to the requirements of IWV-3420?
4.
Provide a clarification of Note '2 of Sec ion I.G. of the Turkey Point IST Program.
5.
Do the emergency diesel generators have an external cooling water system?
6.
Does Turkey Point Unit 3 or 4 util,ize the pressurizer power operated relief valves for low temperature overpressure protection?
7.
Are all valves that are Appendix J, Type C, leak rate tes ed included in the IST Program as Category A or A/C valves?
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8.
Provide two full size copies of the following PEIOs for use at the site meeting:
A.
5610-M-470-5 B.
5610-i 1-4 C.
5610-~-1 D.
5610-N-2 E.
5610-M-5 F.
5610- l-11 G.. 56~0-tl'-10 H.
5610-t'l-500-28 9..
With respect to Subsection I.H:
Do system control have required safety
..::..;..fa.i-lv.r4.pos,i-asians,, etc; )?..:
10.
Is Emergency Service Hater supplied (See Drawing No. 5610-H-6).
any valves. which are used for functions (i.e., required from Unit 2?
B.
Reactor Coolan't S s.em 1.
Relief requests 1 and 2 state that exercising valves CY-3-519A and 3-519 during power operation would cause a loss of containment integrity.
Are these valves not periodical,ly opened during power operation for level control;in the pressurizer relief tank and makeup to the RCP's stand'pipes?
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C.
Chemical and Volume Control S
stem.
1 ~
How does exercising valves CV-3-200A, B, and C during power operation, interrupt flow to the Reactor Coolant Pump Controlled Leakage Seal System?
2.
How does exercisino valves CY-3-310A and B,during power operation interrupt flow to the Reactor Coolant Pump, Controlled Leakage Seal System?
3.
Provide more specific technical information for not, full stroke exercising the following valves quarterly during power operation.
'LCV-3-115B MOV-3-350 3-351 3-357 4.
Review any safety related functions of. the boric acid transfer pump discharge check valves 397A and 8 to determine if they should be included in the 1ST Program.
0.
Safet injection S stem 1.
Provide a more specific technical justification for not full stroke exercising valves MOV-3-860A & B and 'MOV-3-861A 5 B
quarterly during power operation.
2.,
Provide a more specific technical justification for not full stroke exercising valve MOV-3-872 quarterly durino power operation.
3.
Provide a more specific technical justification for not full stroke exercising valve CV-3-855 quarterly during power operation.
4.
How are valves 3-875A, B,
and C full stroke exercised during cold shutdowns?
5.
If valves MOV-878A and B cannot be exercised during cold shutdown if other unit is operating, how can they be exercised during refueling outages if the other unit is operating?
6.
How does shutting valves MOV-3-864A and B, during cold shutdown, jeopardize the High Pressure Safety Injection System?
7.
Are both normally open valves MOV"3"862A and B shut during cold shutdown to facilitate use of the residual reheat removal system?
8.
Have any of the following valves been disassembled, to inspect the valve's internals and to physically verify the valves freedom of motion (-refer to Safety Injection relief, request No.
14)?
3"2918 3-2919 3'"2920 3"890A 3-2921 3"2922 3-2923 3"89GB 9.
How are val,ves 3-875D, E,
and F full stroke exercised during refueling outages?
10.
How are valves
- 879A, B,
C, and D partial stroke exercised quarterly during the associated pump tests?
ll.
Is the Boron Injection Tank maintained under continuous recirculation?
12.
Review any safety related functions of valves 3-856A and B to determine if they should be included in the IST Program.
13.
Are Category A valves MOV-3-880A and
.B leak rate tested?
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E.
Auxiliar Coolant Component Cool in Water S stem
.1.
What-is the safety related function of. valves CV-3-739 and 3-738,
-component cooling water from and to, the excess letdown heat exchanger?
F..
Sam lin S stem 1.
Are valves CV-3-956A, 8, C,
and 0 periodically opened during power operation to facilitate sampling the associated'ystems?
2.
Oo the following valves perform a containment isolation func.ion?
3-951 3-953 3-955A, 8, C, 0, and E
1,
, Provide, the. specific. techni'cal justification) for not stroke timing valves CV-2046A and B.
H.
Condensate and Feedwater S stems 1.
Are the following valves always open during power operation?
MOV-3-1425 MOV"3-1426 MOV"3-1427 CV-3-6275A CV-3-62758 CV"3-6275C 2.
Review any safety related functions of the following valves to determine if they should be included in the IST Program.
MOV-1407 Feedwater Startup Flow Control MOV-1408 Feedwater Startup Check MOV-1409 Feedwater Startup Check
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I.
Service Air S stem 1.
How is valve 3-40-205 verified shut, its safety related position, during co'id shutdown?
2.
Provide the P&ID that shows valve 3-40-203.
J.
Auxil:ar Coolant
Does valve MOV-4-751 perform a containment isolation function?
).
Does Unit 3.have valves comparable to 4"BA-201 and CV-4"6165, breathing air containment isolation valves, in Unit 4?
L.
Main Steam S stem 1 ~
Review any safety related functions of the foll'owing valves to determine if they should be included in the 1ST'rogram.
MOV-1400 004 MOV-1401.
005 MOV-1402, 006
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1.
Subsection II.B refers to a relief request from the requirements of IWP-3400; however, that relief request is not included in the program.
Please provide the details of that'equest for relief.
2.
Are any of the following pumps provided with, an emergency power supply2 a.,
Boric Acid Transfer b.
Boron Injection Recirculation c.
Chilled Water d.
Charging e.
Spent Fuel Pool Cooling g.
Diesel Generator Fuel 0'il Transfer h.
Diesel Generator Jacket Water Cooling
~ " '-'-. ---."- 3 '--Is. Note.2.of'able 4 a-request for relief from measuring flowrate in accordance with IWP-31007 4.
Are the following constant speed pumps7 a.
3-P9A, B 8 C
b.
3-P210 A 8 B
c.
3-P211 A, B 5 C
d.
3P214 A 5 8 e.
P215A, B, C8 D
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